摘要
为了研究核供热反应堆主回路自然循环两相流动稳定性，考证了具有密度－核反馈耦合条件下两相流动的热工水力学行为。在热工实验回路ＨＲＴＬ－５中引入了反应堆中子动力学模拟系统。以实测冷却剂密度作为其输入参数，以中子动力学模拟系统的功率输出通过ＨＰ－３８５２５控制器对系统电加热功率进行实时控制，实验研究了不同工况条件下自然循环两相流动的稳定性。研究结果表明，核反馈耦合条件下系统中出现很低欠热度不稳定性区，反馈系数大小、测量系统和元件动态响应特性对自然循环两相流动稳定性有重要影响。
In order to study two phase flow stability of natural circulation in the primary loop of nuclear heating reactors, the thermo-hydraulic behavior of two phase flow with density-neutronics feedback condition was experimentally investigated. A reactor neutron dynamic simulator was introduced in thermo-hydraulic test loop HRTL-5. The density of coolant is used as input signal, and the power output of the neutronics simulator is used to control the heating power of the test section through HP-3852S controller. The two phase flow stability of natural circulation under different conditions was investigated. The results show that an unstable flow region occurs on very low subcooling area under density-neutron feedback condition; feedback coefficient and dynamic response characteristics of measuring system and heated element significantly effect the two phase flow stability.
出处
《清华大学学报（自然科学版）》
EI
CAS
CSCD
北大核心
1995年第6期94-98,共5页
Journal of Tsinghua University(Science and Technology)
关键词
自然循环
核耦合
稳定性
两相流
反应堆
回路
low pressure natural circulation
nuclear coupled stability
two-phase flow
